ML20198G631

Effluent & Waste Disposal Semiannual Rept for First & Second Quarters 1997

ML20198G631
Person / Time
Site:	Yankee Rowe
Issue date:	06/30/1997
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20198G629	List: ML20198G624 ML20198G631 ML20198G638
References
NUDOCS 9709040218
Download: ML20198G631 (22)

Text

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1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR FIRST AND SECOND QUARTERS 1997 i

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i Yankee Atomic Electric Company Rowe, Massachusetts a

CWRT.FFLNT 07A.

8/28/97 9709040218 970829 PDR ADOCK 05000029 R_

PDR

NOTES:

1.-

Yankee Nuclear Power Station's last day at any power level was October 1,1991. The :

facility is permanently shut down and in the process of decommissioning,- Due to ceased operations, short-lived nuclides have been deleted from the gaseous and liquid effluent tables. Their activity concentrations in the fuelinventory have decayed to zero values.

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~ LIST OF TABLES AND APPENDICES l

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-- - TABLE 1 A Gaseous Effluents - Summation of All Releases,................. - 1 4

TABLE 1B.

Gaseous Effluents - Elevated Releases 2

c TABLE 1C L Gaseous Effluents - Ground Level Releases....................

3

-TABLE 2A Liquid Emuents - Summation of All Releases.................,.. - 4 i

TABLE 2B Liquid Emuents - Routine Releases.......,.................... 5

)

TABLE 3 Solid Waste and Irradiated Fuel Shipments...................... 6 L

APPENDIX A Radioactive Liquid Emuent Monitoring instrumentation........... A 1 4

4 APPENDlX B Radioactive Gaseous Emuent Monitoring instrumentation.......... B-1 APPENDIX C Liquid Holdup Tanks...................................... C-1 APPENDIX D Radiological Environmental Monitoring Program................. D-1 4'

APPENDIX E Land Use Census........................................ E-1

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APPENDIX F

. Process Control Program (PCP)............................. F-1 i

APPENDIX G Off-Site Dose Calculation Manual (ODCM),.................... G-1 l-APPENDIX H Radioactive Liquid, Gaseous, and Solid Waste Treatment

- Syste m s.............................................. H..

.' APPENDIX l Supplemental lnformation...................................' l-1 4-i CWREFFLNT.97A N

TABLE 1 A Yankee Atomic Electric Comoany. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters 1997 QFseous Effluents - Summation of All Releases E

Unit Quarter 1 Quarter 2 Er A. Fission and Activation Gases

1. Total Release Cl 0.00e+00 0.00e+00

• 2.50e+ 01

2. Avera0e Release Rate for Period pCl/sec 0.00e+00 0.00e+00

3. Percent of Control Limit")

0.00e+ 00 0.00e+00 B. lodines**

C. Particulates

1. Particulates with half-lives > 3 days Cl 7.09e-07 3 59e-08 t3.00e+01

2. Average release rate for petiod pCi/sec 9.02e-08 4.57e-09

3. Percent of Control Umit'd 6.670-03 6.67e-03

4. Gross Alpha Radioactivity Ci

<9 97e-08

<3.440 08 D. Tritium

1. Total Release Cl 6.26e-02 6.38e-02 t3.00e+01

2. Average Release Rate for Period pCi/sec 7.96e-03 8.12e-03

_ 3. Percent of Control Umit'*

NA NA (a) OCCM Control 3.4.a for gamma-air dose. Percent values for ODCM Centrol 3.4.b for beta-air dose would be approximately the same.

(b). lodine data have been deleted. These nucEdes are no longer available for discharge.

(c) Per ODCM Control 3.5, the percentage of the imit is based on the combined dose contribution from iodnes, tntium, and particulates with half Eyes greater than 8 days. Percentage oflimits are calculated using ODCM Method I dose equations.

(d) Per ODCM Control 3.5, percentage dose contribution from tritium is included in Part C.3. saare7 cwms:Frtwt e7A

TABLE 1B Yankee Atomic Electric Cornosov Rowe Massachusetts Ehtuent and Waste Disposal Semiani,ual Report First and Second Quarters 1997 Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode'*

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 g

1. Fission Gases Kryptort S$

Cl 0.00e+00 0.00e+00 Total for Period Ci 0.00e+00 0.00e+ 00

2. lod!nes")

3. Particulates Strontium-89 Ci

<3.01 e-06

<5.15e-07 Strontium-90 Ci

<1.24e-06

<2.41 e-07 Cesium-134 Ci

<011e-07

<4.03e-07 Cesium-137 Ci

<1.18e-06 3.59e-08 Zine-65 Ci

<2.41 e-06

<1.35e-06 Cobalt-58 Ci

<9 650-07

<3.42e-07 Cobatt-60 Cl 7.09e 07

<5.46e-07 Zirconium-Niobium-95 Ci

<1.67e-06

5.62e-07 Cerium-144 Ci

<3.36e-06

<1.10e-06 Antimony-124 Ci

<8.97e-07

<5.26e-07 Manganese-54 Cl

<1.07e-06

<3.53e-07 Sliver-110m Ci

<9 55e-07

<1.07e-06 Total for Period Ci 7.09e-07 3 59e-08 (a) There are no longer any batch mode gaseous releases.

(b) lodine-131, lodir+ 133, and lodine-135 activities have been deleted. These nuclides are no longer available for discharge.

CWREFFLNTErA e<2arer

TABLE 1C-Yankee Atomic Electric Company. Rowe. Massachusetts t-Effluent and Waste Disposal Semiannual Report Firci and Second Quarters 19E l

Gaseous Effluents - Ground Level Releases r

There were no routine measured ground level continuous or batch mode gaseous releases during the first or second quarters of 1997, i-

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TABLE 2A Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semlannual Report First and Second Quarters 1997 Liould Effluents - Summation of All Releases E

Unit Quarter 1 Quarter 2 Er A. Fission and Activation Products

1. Total Release (not including tritium, gases, afpha)

C1 2.44e-06 5 27e-06

• 2.00e+ 01

2. Average Diluted Concentration During Period pC cnl 2.00e-11 6.30e-11

3. Percent of Applicable UmW 6.67e-05 7.86e-05 B. Tritium

1. Total Release Cl 3.74e-03 6.52e-02 s 1.00e+01

2. Average Diluted Concentration During Period pCi/ml 3.07e-08 7.79e-07

3. Percent of Applicable ump 1.02e-03 2.60e-02 C. Dissolved and Entrained Gases

1. Total Release Ci

<4.17e-04

<5.74 e-04

• 2.00e+01

2. Average Diluted Concentration During Period pCi/mi

<3.420-09

<6.86e-09

3. Percent of Applicable Limita*

<1.71 e-03

<3.43e-03 D. Gross Alpha Radioactivity

1. Total Release Cl

<1.70e-07

<1.10e-07 13.50e+01 E. Volume of Waste Release (prior to dilution)

Eters 3.29e+05 2.31e+05 23.00e+01 F. Volume of Dilution Water Used During Period Eters 1.22e+08 8.37e+07

• 1.50e+01 (a) Concentration Emits specified in Appendix B to 10CFR20.1-20.602, Table il, Column 2 (OOCM Control 2.1).

The percent of applicable Emit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration Emit.

(b) Concentration Emits for dissolved and entrained noble gases is 2.00E-04 pCi/mi(ODCM Control 2.1). The percent of applicable Emit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration Emit.

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TABLE 2B Yankee Atomic Electric Company. Rowe. Massachusetts i

Effluent and Waste Disposal Semiannual Report 1

First and Second Quarters 1997 Liauid Effluents - Routine Releases Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Strontium-89 Ci

<4.35e-06

<2.78e-07

<6.95e-06

<7.47e-06 Strontium-90 Cl

<1.90e-06

7.94e-08

<2.90e-06

<2.55e-06 Cesium-134 Cl

<5.14e-07

<6.57e-08

<7.07e-07

<103e.06 Cesium-137 Ci

<6 80e-07

<8.83e.08

<8.98e-07 1.80e-07 Cobett.58 Ci

<6.14e-07

<9 39e-08

<8.18e-07

<1.15e-06 Cobatt-60 C1 2.44e-06 3.728-06

<1.05e-06 1.27e-06 Iron-59 Ci

<1.20e-06

<1.38e-07

<1.63e-06

<2.43e-06 Zine-65 Ci

<1.41 e-06

<2.18e-07

<1.76e-06

<2.81 e-06 Manganese-54 Ci

<6.79e-07 8.83e-08

<8.37e-07

<1.27e-06 Zirconium-Niobium-95 Ci

<1.02e-06

<1.45e-07

<1.420-06

<2.10e-06 Molybdenum-99 Ci

<4.31046

<5.42e-07

<6.02e 06

<8.01 e-06 Cerium-144 Ci

<3.12e-06

<3.14e-07

<4.35e-06

<6.50e-06 Silver-110m Ci

<5.47e-07

<7.00e-08

<7.32e-07

<1.11 e-06 Antimony-124 Ci

<5 22e-07

<6 77e-08

<7.15e-07

<1.18e-06 Carbon-14 C1

<1.40e-05

<8.07e-06 fron Ci

<6.80e-05

<2.00e-06

<7.53e-35

<8.52e-05 Antimony-125 Ci

<1.50e-06

<1.74e-07

<1.998-06

<2.000-06 Unidentified Ci Total for Period (above)

Ci 2.44006 3.81 e-06

<1.22e-04 1.46e-06 Krypton-85 Ci

<1.73e-4

<1.49e-05

<2.44e-04

<3.30e-04

• b 6/2fVU7 CWRtFFLNT 97A

4 TABLE 3 (Sheet 1 of 2)

. Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Quarters 1997 Solid Waste and Irradiated Fuel Shloments A. SOUD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (not Irradiated fuel)

Srn nm Est tow

1. Type of Waste Unit Penod Error, %

1 a.

Dry Active Wate: Class A m'

1.14e+01 2.50e01 Containers: steel box (101 ft')

CI(Est) 9.80e-03 b.

Dry Active Waste: Class A m'

1.70e+01 2.50e+01 Containers:(a)

I Ci(Est) 2.64e-01 c.

Irradiated Components: Class A m'

4.56e+01 2.50e+01 Containers: steel Ener (201 ft'), steel box (101 ft')

CI(Est) 3.55e+01 d.

Irradiated Components: Class B m'

1.12e+ 02 2.50e+01 Containers: reactor pressure vessel cask (3,952 ft')

C1(Est) 3.03e+03

2. Estimate of Nuclide Ccmposition > 1% (by type of waste) d a.

Iron-55 6.33e+01 Cobalt-60 2.01 e+01 Nickel-63 1.50e+01 b.

Iron-55 6.44e+01 Cobalt-60 2.?ie+01 2

Nickel-63 1.05e+01

c..

Iron-55 8.84e+01 Coba % 0 1.07e+01 d.

Iron-55 6.63e+01 Cobalt-60 2.66e+0i Nickel-63 6 80e+00 a w er c m n m e7A

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I TABLE 3' (Sheet 2 of 2)

Yankee Atomic Electric Company. Rowe. Massachusetts Emuent and Waste Disposal Semiannual Report First and Second Quarters 1997 Solid Waste and Irradiated Fuel Shloments -

3. solid Weste Disposition 4 -

Number of Shioments Mode of Transoortation Destination 7

truck Barnweg, SC 1

-34(a).

truck /ral Bamweg, SC

. truck Bamwel, SC 2(a)

= truck So. Cive. UT 18(b) truck Oak Ridge, TN 11(b) truck Memphis, TN B. IRKADIATED FUEL SHIPMENTS (Disposition): None I

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(a) Partial shipmeats by the processor to disposal (b) Waste shipments to processor.

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APPENDIX A.

Radioactive Llauld Efftv9nt Monitorina Instrumentation

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L Reauirement:

Radioactive liquid effluent monitoring instrumentatio6: channels are' required to be operable in accordance with ODCM Control 5.1._ With less than the minimum number of channels operable and reasonable efforts to retum the Linstrument(s) to operable status within 30 days being unsuccessful, ODCM _

Control 5.1 requires an explanation for the delay in correcting the inoperability

. in the next Effluent and Waste Disposal Semiannual Report.

- Response:

As part of the plant's dismantlement and decommissioning process, the Turbine Building Sump composite sampler, located on the 002 discharge pathway, was permanently removed from service on June 2,1997. On that -

date, the service water pumps were permanently secured from service,.

resulting in the cessation of water flow via the 002 pathway. Chemistry confirmed by inspection that flow via the 002 outflow pipe had been

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terminated. Additionally, auxiliary boiler and air conditioning equipment that also had drains associated with tne 002 discharge have been similarly removed from service. All remaining drains in the Turbine Building have been plugged to assure that no inadvertent releases occur via the 002 pathway.

ODCM Tables 2._1 and 5.1 state the analysis and compositing sample requirements for plant effluent surveillances. These requirements are -

necessary only when releases are occurring via the appropriate effluent release points. Therefore, with the securing of the 002 pathway, no continued operation of the Turbine Building Sump composite sampler is required.

Reference to the Turbine Building Sump composite sampler will be deleted from ODCM Control 5.1 in an upcoming change to the ODCM.

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APPENDIX B Radioactive Gaseous Effluent Monitorina instrumentation Reauirement:

Radioactive gaseous effluent monitoring instrumentation channels are -

required to be operable in accordance with ODCM Control 5.2. With less than the minimum number of channels operable and reasonable efforts to retum the instrument (s) to operable status within 30 days being unsuccessful, ODCM -

- Control 5.2 requires an explanation for the delay in correcting the inoperability in the next Effluent and Waste Disposal Semiannual Report.

Response

The requirements of ODCM Control 5.2 goveming the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period.

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APPENDIX C r

- Qquid Holduo Tanks Reouirement:

Defueled Technical Specification 3.4 limits the quantity of radioactive insterial contained in any outside temporary tank. With the quantity of radioactive --

- material in e iy outside temporary tank exceeding the limits of Technical J

1 Specification d.4, a description of the events leading to this condition is j'

required in the next Effluent and Waste Disposal Semiannual Report.

- Response-The limits of Technical Specification 3.4 were not exceeded during this reporting period.

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APPENDlX D Radiolooical Environmental Monitorino Prooram Reouirement:

The Radiological Environmental Monitoring Program is conducted in accordance with ODCM C;ntrol 4.1. With milk or fresh leafy vegetation samples no longer available from one or more of the required sample locations, ODCM Control 4.1 requires the identification of the new location (s) for obtaining replacement sample (s)in the next Effluent and Waste Disposal Semiannual Report and inclusion of revised Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new location (s).

Response

No milk or fresh leafy vegetation samples were found to be unavailable during 4

this reportinc period.

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APPENDIX E Land Use Census Reauirement:

A land use census is conducted in accordance with ODCM Control 4.2. W?h a land use census identifying a location (s) whKr. yields at least a 20 percent greater dose or dose commitment than the values currently being calculated ir.

ODCM Control 3.5; ODCM Control 4.2 requires the identification of the new location (s) in the next Effluent and Waste Disposal Semiannual Report.

Response

The annualland use census is scheduled for completion during the second half of 1997.

Reauirement:

With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which samples are currently being obtained in -.

accordance with ODCM Controi 4.1, ODCM Control 4.2 requires that the new location (s) be added to the Radiological Environmental Monitoring Program if permission from the owner to collect samples can be obtained and sufficient sample volume is available. The identification of the new location (s)is required in the next Effluent and Waste Disposal Semiannual Report.

Response

The annualland use census is scheduled for completion during the second half of 1997, E-1 anam e m m ur m

APPENDIX F i

Process Control Proaram (PCP) --

I fleauirement:

PCP Control 2.0 requires that licensee-initiated changes to the PCP be -

submitted to the Commission in the Effluent and Waste Disposal Semiannual -

Report for the period in which the change (s) was made.

Response

There wre no licensee-initiated changes to the PCP during this reporting

. period, 1

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1 APPENDIX G Off Site Dose Calculation Manual (ODCM)

Reouirement:

ODCM Control 7.2 requires that licensee-lnitiated changes to the ODCM be submitted to the Commission in the Effluent and Waste Disposal Semiannual Report for the period in which the change (s) was made effective.

Response

Revision 12 to the Yankee Offsite Dose Calculation Manual (ODCM) was issued during this reperting period. This revision eliminaied the commitmunt to compile annual onsite meteoroio0ical data summaries for inclusion in the Semiannual Radioactive Effluent Release Report. Revision 12 to the Yankee ODCM was approved by PORC in meeting No. 97-3, January 9,1997, and is attached in its entirety.

The data collected by the onsite meteorological tower were once used io generate an annual assessment of offd'a doses resulting from gaseous releases. During plant operation, batch (discrete) ahteme releases were modeled using meteorological conditions concurrent with the time of release and continuous airborne releases were modeled using quarterly average meteomlogical conditions concurrent with the quarterly release period.

Since the Yankee Plant has ceased power operation and is in the later stages of decommissioning, potential gas source terms have decayed and the gas holdup system has been opened and dismantled. Subsequently, batch gas releases have been eliminated. All remaining airborne releases are now considered continuous and are reported as quarterly totals in the Semiannual Effluent Release Report. Since long-term histor; cal meteorology is expected to provide a reasonable estimate of actual quarterly average atmospheric dispersion factors (CHl/Q values), Revision 11 to the ODCM permits the use of historical average meteorological conditions to determine the gaseous pathway doses. Because the ODCM no longer requires the use of concurrent meteorological data to perform offsite dose assessments, it is no longer meaningful to include these data as part of the Semiannual Effluent Release Repvrt.

This change to the ODCM reflects the shutdown status of the plant and the ongoing decommissioning of the facility. The change does not reduce the affective level of radioactive effluent control and monitoring of release pathways that still represent a potential effluent source term.

Decommissioning activities have removed various potential sources Song veh the natural radioactive decay of relatively short lived radionut s fue to the cessation of the fisslan process in October,1991, (almost 6 years ago). It is therefore concluded that this change to the ODCM will continue to maintain the level of radioactive effluent control required by 10CFR 20.106 (new 20.1301),40 CFR 100,10 ',FR 50.36a, and Appendix l to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent measurements, or dose and setpoint calculations.

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i APPENDIX H Radioactive Liould. Gcseous. and Solid Waste Treatment Systems

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E3auirement:-

. ODCM Control 7.3 requires that licensee-initiated major changer to the -

_ radioactive waste systems (liquid, gaseous, and solid) be reported to thei Commisision in the Effluern and Waste Dispocal Semiannual Report for the

'a period in wNch the evaluation was reviewed by the Plant Operation Review Committee.

Rg_sponse:

During April,1997, charcoal filter material was permanently removed from the F

non-safety class Ventilation Exhaust Treatment System as part of the plant's-J dismantlement and decommissioning operations. Since the cessation of power operations in October,1991, the production of iodine due to the fission g

process no longer takes place. In addition, due to the sh;-t 8.05 day half life of lodine-131, as well as that of lodine-133 (20.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />), tne lodine source j

term in plant systems, including the potential source in the spent fuel, has -

been eliminated through the process of radioactive decay. As a result, the -

[

charcoal absorbers in the Ventilation Exhaust Treatment System, which were -

included in the original design specifically for iodine absorbing, are no longer needea for exhaust filtration since the radionuclide species that it was i

p inonded to treat are no longer a component of routine effluent releases.

L The FSAR does not credit any filtration device to reduce or mitigate the C

consequences of hypothetical accidents. FSAR Section 231 states that "The

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Ventilation System, with the exception of the charcoal filters, is required to support plant operations during the safe storage period." Therefore, removing the charcoal does not change the basis of the FSAR. The HEPA 5

and pre-HEPA filters for the treatment of airbome particulate radioactivity remain in servico in that portion of the Ventilation Exhaust Treatment System.

The primary reason for removing the charcoal filter banks was to facilitate i

dscommissioning work. Fire detection was originally provided for the charcoal filter banks located in the Primary Auxiliary Building (PAB) Fan Room.

Removal of the fire de'ection from the PAB Filter Banks was desired in order 1

L to allow the removal of the associated cable as part of the dismantlement E

activities.

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~ The Ventilation Treatment System, which originally consisted of two parallel j ;

trains of charcoal absorber sections, pre-filters, and HEPA filters, provided air -

filtration during past power operations from primary side areas that could

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potentially be contaminated before exhausting the ventilation flow to the

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environment via the Primary Vent Stack. One exhaust train normally was l.

aligned to the Vapor Container, while the second train treated exhaust air from i

the Primary Auxiliary Building, Waste Disposal Building,' Spent Fuel Pool -

. Building, and the Temporary. Liquid Waste Processing System. The charcoal i.

absorber portion of each train was comprised of a one-inch sacrificial activated carbon section and a four-inch imprsgnded activated carbon bed.

The purpose of the sacrificial carbon was to remove atmospheric vapors such

. as paint and welding fumes, while the impregnated carbon was intended for radioiodine removal. The charcoal was vacuumeci removed from the filter

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Since the iodine source term that the charcoal filter media was intended to -

- treat has been eliminated, the removal of the charcoal media will not result in any change to the reported airbome effluents and resulting doses to members of the public and will not result in increased occupational exposures to the plant staff. Predicted releases of radioactivity would remain the same to that -

of actual releases for the period prior to the rernoval of the charcoal 1

Occupational exposures continuo to be minimized, monitored, and controlled -

in strict compliance with existing plant procedures. The ALARA program i'

- continuss io implemented throughout the decommissioning process. The program ensures that ALARA is considered in all aspects of plant operation, maintenance, inspection, and modification.

The system change that allowed the removal of the charcoal media was reviewed and found acceptable by PORC on April 15,1997 as documented in i

PORC meeting number 97-31.

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APPENDIX l Supplemental Information First and Second Quarters 1997.

1.'

Control Limits - Dose and Dose Rata 1

Control and Cateoory Mmil i

a.

Noble Gases Control 3.3, Total body dose rate 500 mrem / year Control 3.3, Skin dose rate 3000 mrem / year Control 3.4, Gamma air dose 5 mrad / quarter Control 3.4, Gamma air dose 10 mrad / year Control 3.4, Beta air dose 10 mrad / quarter Control 3.4, Beta air dose 20 mradlyear b.

lodine-131. Tritium. and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Da.y.1 s

. Control 3.3,' Organ dose rate 1500 mrem / year j

Control 3.5, Organ dose 7.5 mrem / quarter Control 3.5, Organ dose 15 mrem / year c.

Liauids Control 3.1, Total body dose 1.5 mrem / quarter j

Control 3.1, Total body dose 3 mrem / year Control 3.1,- Organ dose 5 mrem / quarter Control 3.1, Organ dose 10 mrem / year 3-i C. N N 97A N

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2.

Control limits - Concentration 1

Control and Cateoorv -

' Mmh s.

Liauids

. Control 2.1. Total sum of the fraction of MPC (10CFR20, 1.0 L

' Appendix B, Table ll, Column 2), excluding noble gases less than:

- Control 2.1, Total noble gas concentration -

2.00E-04 pCi/cc 3.

' Measurements and Aporoximations of Total Radioactivity -

.t a.

. Noble' Gases. Krvoton-85

- Continuous discharges are determined by direct measurements. ' A primary vent.

4-stack gas sample is taken monthly and analyzed for Krypton-85. A review of the weekly primary vent stack noble gas integrator readings for any increase in values above the background level also is used as a reference. There are no longer any

_ batch dischages. Errors associated with the above measurements are estimated 4

to be *25 percent.-

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lo(nes. Particulates t

)

There' are no longer any iodine isotopes available for dischstge. - The sampling i

system design requires the use of a charcoal cartridge as a support for the particulate filter during particulate collection. The sampling system continuously draws a sampl6 from the primary vent stack through a filter and charcoal-cartridge. The particulate filter is removed and analyzed weekly. The errors associated with the determination of particulate effluents are estimated to be *30 percent.

c.

Liouid Effluents L

A gamma isotopic analysis is performed on a representative sample using a

Marinelli Beaker geometry for both a batch or continuous discharge. Composite -

E samples for batch and continuous discharges are analyzed for strontium-89, p

strontium-90, iron-55, gross alpha activity, and carbon-14.-

4 Tritium analysis is performed on composite samples for continuous discharges and on each batch diacharge.- The errors associated with these measurements -

are as follows: fission and activation products, *20 percent; tritium, *10 percent; dissolved fission gases, *20 percent; and alpha activity, i35 percent.

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' Batch Releases a.

Liouids The batch release data is presented in two categories to provide accurate average discharge rate values.

1 Outdoor Routine Tank 4

First Qitarter Batche.1 Moats Number of batch releases:

7 1

Total time period for batch releases (minutes):

8828 240 Maximum time period for a bate's reiease (minutes).

1578 240 Average time period for batch re! cases (minutes):

1261 240 Minimum time period for a batch release (minutes):

1080 240 Average stream flow (Sherman Dam) during penod (cfs):

1030 1030 Average discharge rate (gpm):

5.6 6.2 Outdoor Routine Tank 4

Second Quarter Batches Moats Number of batch releases:

6 8

Total time period for batch releases (minutes):

7244 6883 Maximum time period for a batch release (minutes):

1515 2743 Average time period for batch releases (minutes):

1207 860 Minimum time period for a batch release (minutes):

160 315 Average stream flow (Shermar. Dam) during perior' (cfs):

649 649 Average discharge rate (gpm):

4.4 3.9 b.

Gases There are no longer any gaseous batch discharges.

5.

Abnormal Releases ODCM Control 7.2 requires the reporting of any unplanned releases from the site to the site boundary of radio.tctive materialin gaseous and liquid effluents made during the reporting period.-

a.

Liauid There were no nonroutine liquid releases during the reporting period.

b.

Gases There were no nonioutine gaseous releases during the reporting period.

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